Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Effect of error field correction coils on W7-X limiter loads

Journal Article · · Nuclear Fusion
 [1];  [1];  [1];  [2];  [3];  [1];  [4];  [1];  [5];  [6];  [4];  [1];  [1];  [1]
  1. Max-Planck-Institut fur Plasmaphysik, Greifswald (Germany)
  2. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  3. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  4. Wigner Institute, Budapest (Hungary)
  5. Univ. of Cagliari (Italy)
  6. Univ. of Wisconsin, Madison, WI (United States)
In the first campaign Wendelstein 7-X was operated with five poloidal graphite limiters installed stellarator symmetrically. In an ideal situation the power losses would be equally distributed between the limiters. The limiter shape was designed to smoothly distribute the heat flux over two strike lines. Vertically the strike lines are not uniform because of different connection lengths. In this paper it is demonstrated both numerically and experimentally that the heat flux distribution can be significantly changed by non-resonant $n=1$ perturbation field of the order of $$10^{-4}$$ . Numerical studies are performed with field line tracing. In experiments perturbation fields are excited with five error field trim coils. The limiters are diagnosed with infrared cameras, neutral gas pressure gauges, thermocouples and spectroscopic diagnostics. Experimental results are qualitatively consistent with the simulations. With a suitable choice of the phase and amplitude of the perturbation a more symmetric plasma-limiter interaction can be potentially achieved. Finally, these results are also of interest for the later W7-X divertor operation.
Research Organization:
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
Sponsoring Organization:
EUROfusion Consortiumand has received funding from the Euratom research and training programme 2014-2018 under grant agreement No 633053.; USDOE
Contributing Organization:
W7-X Team
OSTI ID:
1466524
Alternate ID(s):
OSTI ID: 22925954
Journal Information:
Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 12 Vol. 57; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English

References (15)

3D Edge Modeling and Island Divertor Physics journal April 2004
Service oriented architecture for scientific analysis at W7-X. An example of a field line tracer journal November 2013
A high resolution IR/visible imaging system for the W7-X limiter journal August 2016
Overview of diagnostic performance and results for the first operation phase in Wendelstein 7-X (invited) journal October 2016
The capabilities of steady state operation at the stellarator W7-X with emphasis on divertor design journal June 2000
Tracking of the magnet system geometry during Wendelstein 7-X construction to achieve the designed magnetic field journal May 2015
Methods for measuring 1/1 error field in Wendelstein 7-X stellarator journal June 2016
Transport in stellarators journal December 1993
Energy flux to the ASDEX-Upgrade diverter plates determined by thermography and calorimetry journal January 1995
Major results from the stellarator Wendelstein 7-AS journal March 2008
Setup and initial results from the magnetic flux surface diagnostics at Wendelstein 7-X journal May 2016
Numerical investigation of plasma edge transport and limiter heat fluxes in Wendelstein 7-X startup plasmas with EMC3-EIRENE journal January 2017
Error field measurement, correction and heat flux balancing on Wendelstein 7-X journal March 2017
Limiter observations during W7-X first plasmas journal April 2017
The Trim Coils for the Wendelstein 7-X Magnet System journal June 2012

Cited By (6)

Magnetic configuration effects on the Wendelstein 7-X stellarator journal May 2018
Wall conditioning by ECRH discharges and He-GDC in the limiter phase of Wendelstein 7-X journal April 2018
Measurements and correction of the 1/1 error field in Wendelstein 7-X journal December 2018
Methods for quantitative study of divertor heat loads on W7-X journal April 2019
Features of near and far scrape-off layer heat fluxes on the Wendelstein 7-X inboard limiters journal November 2019
Magnetic configuration effects on the edge heat flux in the limiter plasma on W7-X measured using the infrared camera and the combined probe journal April 2018

Similar Records

Error fields in the Wendelstein 7-X stellarator
Journal Article · Thu Nov 08 19:00:00 EST 2018 · Plasma Physics and Controlled Fusion · OSTI ID:1484166

Error field measurement, correction and heat flux balancing on Wendelstein 7-X
Journal Article · Thu Mar 09 19:00:00 EST 2017 · Nuclear Fusion · OSTI ID:1353402

First measurements of error fields on W7-X using flux surface mapping
Journal Article · Tue Aug 02 20:00:00 EDT 2016 · Nuclear Fusion · OSTI ID:1335163